Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Takada, Shoji; Honda, Yuki*; Inaba, Yoshitomo; Sekita, Kenji; Nemoto, Takahiro; Tochio, Daisuke; Ishii, Toshiaki; Sato, Hiroyuki; Nakagawa, Shigeaki; Sawa, Kazuhiro*
Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7 Pages, 2018/10
Nuclear heat utilization systems connected to HTGRs will be designed on the basis of non-nuclear grade standards for easy entry of chemical plant companies, requiring reactor operations to continue even if abnormal events occur in the systems. The inventory control is considered as one of candidate methods to control reactor power for load following operation for siting close to demand area, in which the primary gas pressure is varied while keeping the reactor inlet and outlet coolant temperatures constant. Numerical investigation was carried out based on the results of nuclear heat supply fluctuation tests using HTTR by non-nuclear heating operation to focus on the temperature transient of the reactor core bottom structure by imposing stepwise fluctuation on the reactor inlet temperature under different primary gas pressures below 120C. As a result, it was emerged that the fluctuation absorption characteristics are not deteriorated by lowering pressure. It was also emerged that the reactor outlet temperature did not reach the scram level by increasing the reactor inlet temperature 10 C stepwise at 80% of the rated power as same with the full power case.
Fujita, Takaaki; JT-60 Team
Nuclear Fusion, 46(3), p.S3 - S12, 2006/03
Times Cited Count：8 Percentile：28.05(Physics, Fluids & Plasmas)no abstracts in English
Umeda, Naotaka; Yamamoto, Takumi; Hanada, Masaya; Grisham, L. R.*; Kawai, Mikito; Oga, Tokumichi; Akino, Noboru; Inoue, Takashi; Kazawa, Minoru; Kikuchi, Katsumi*; et al.
Fusion Engineering and Design, 74(1-4), p.385 - 390, 2005/11
Times Cited Count：9 Percentile：53.19(Nuclear Science & Technology)In negative ion based neutral beam injector (N-NBI) for JT-60U, some modifications for extent pulse duration from 10 second, which is design value, to 30 second was conducted. Main limit to prevent pulse extension was heat loads onto grounded grid in an ion source and onto beam limiter placed at 22 m from the ion source. To reduce these heat loads, beam extraction area was optimized and the limiter was changed to one which had about twice thermal capacity. As a result of these modifications, the temperature rise of the water which was cooling grounded grid could be suppressed under 40 degree, which can operate in steady state condition. The temperature rise of the limiter could be restricted to 60%. Untill now the beam pulse extended to 17 second of 1.6MW power at 366keV energy, and injection of 30 seconds will be achieved in next experiment.
Ebisawa, Noboru; Akino, Noboru; Kazawa, Minoru; Komata, Masao; Mogaki, Kazuhiko; Seki, Norikazu*; Oga, Tokumichi; Ikeda, Yoshitaka
Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03
no abstracts in English
Mogaki, Kazuhiko; Kawai, Mikito; Kazawa, Minoru; Komata, Masao; Umeda, Naotaka; Ikeda, Yoshitaka
Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03
no abstracts in English
Ishiyama, Shintaro
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(3), p.288 - 297, 2004/09
Target plate mode of divertor device for fusion reactor was fabricated using low activated and light material, Si/xSiC metal matrix composite and high strength and thermal conductive SiC. This model was exposed under 5MW/m
30sec high heat flux and showed very good cooling performance and no damage was found after this test.
Uda, Minoru*; Iwadachi, Takaharu*; Uchida, Munenori*; Yamada, Hirokazu*; Nakamichi, Masaru*; Kawamura, Hiroshi
JAERI-Conf 2004-006, p.60 - 65, 2004/03
no abstracts in English
Takano, Shoji*; Totsuka, Toshiyuki; Yonekawa, Izuru
KEK Proceedings 2003-16 (CD-ROM), 4 Pages, 2004/02
no abstracts in English
Shiina, Yasuaki; Nishihara, Tetsuo
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.418 - 427, 2003/12
no abstracts in English
Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.
Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12
Times Cited Count：101 Percentile：93.45(Physics, Fluids & Plasmas)no abstracts in English
Hatano, Toshihisa; Kuroda, Toshimasa*; Barabash, V.*; Enoeda, Mikio
Journal of Nuclear Materials, 307-311(2), p.1537 - 1541, 2002/12
Times Cited Count：4 Percentile：29.25(Materials Science, Multidisciplinary)no abstracts in English
Uchida, Munenori*; Ishitsuka, Etsuo; Hatano, Toshihisa; Barabash, V.*; Kawamura, Hiroshi
Journal of Nuclear Materials, 307-311(Part2), p.1533 - 1536, 2002/12
Times Cited Count：3 Percentile：23.41(Materials Science, Multidisciplinary)no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
International Journal of Heat and Mass Transfer, 45(20), p.4107 - 4115, 2002/09
Times Cited Count：44 Percentile：80.92(Thermodynamics)no abstracts in English
Tamai, Hiroshi; Yoshino, Ryuji; Tokuda, Shinji; Kurita, Genichi; Neyatani, Yuzuru; Bakhtiari, M.; Khayratdinov, R. R.*; Lukash, V.*; Rosenbluth, M. N.*; JT-60 Team
Nuclear Fusion, 42(3), p.290 - 294, 2002/03
Times Cited Count：34 Percentile：70.69(Physics, Fluids & Plasmas)no abstracts in English
Asakura, Nobuyuki; Loarte, A.*; Porter, G.*; Philipps, V.*; Lipschultz, B.*; Kallenbach, A.*; Matthews, G.*; Federici, G.*; Kukushkin, A.*; Mahdavi, A.*; et al.
IAEA-CN-94/CT/P-01, 5 Pages, 2002/00
Three important physics issues for the ITER divertor design and operation are summarized based on the experimental and numerical work from multi-machine database (JET, JT-60U, ASDEX Upgrade, DIII-D, Alcator C-Mod and TEXTOR). (i) The energy load associated with Type-I ELMs is of great concern for the lifetime of the ITER divertor target. In order to understand the physics base of the scaling models, the ELM heat and particle transport to the divertor is investigated. Convective transport during ELMs plays an important role in heat transport to the divertor. (ii) Determination of the SOL flow pattern and the driving mechanism has progressed experimentally and numerically. Influences of the drift effects on the SOL and divertor plasma transport were discussed. (iii) Characteristics of chemical yield at two different deposited carbon surfaces, i.e. erosion- and redeposition-dominated areas, have been studied. Progress of understanding the chemical erosion is reviewed.
Ishitsuka, Etsuo; Uchida, Munenori*; Sato, Kazuyoshi; Akiba, Masato; Kawamura, Hiroshi
Fusion Engineering and Design, 56-57, p.421 - 425, 2001/10
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)no abstracts in English
Seki, Masami; Maebara, Sunao; Fujii, Tsuneyuki
Fusion Engineering and Design, 56-57, p.581 - 585, 2001/10
Times Cited Count：2 Percentile：19.66(Nuclear Science & Technology)no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime
Nihon Kikai Gakkai Rombunshu, B, 67(662), p.2550 - 2557, 2001/10
no abstracts in English
Sato, Kazuyoshi; Ishitsuka, Etsuo; Uchida, Munenori*; Kawamura, Hiroshi; Ezato, Koichiro; Taniguchi, Masaki; Akiba, Masato
Physica Scripta, T91, p.113 - 116, 2001/07
Times Cited Count：1 Percentile：11.96(Physics, Multidisciplinary)no abstracts in English
; ; Ueno, Fumiyoshi; ; ; ;
JNC TN2400 2000-005, 103 Pages, 2000/12
JNC-TN2400-2000-005.pdf:3.98MB
Inelastic analyses of the floor liner subjected to thermal loading due to sodium leakage and combustion were carried out, considering thinning of the liner plate due to molten salt type corrosion. Because the inelastic strain obtained by the analyses stayed below the ductility limit of the material, mechanical integrity, i.e., there exist no through-wall crack on the floor liner, was confirmed. Partial structural model tests were conducted, with a band of local thinning of the liner plate. Displacements were controlled to give specimens much larger strains than those obtained by the inelastic analyses above. No through-wall crack was observed by these tests. Mechanical integrity of the floor liner was confirmed by these results of the inelastic analyses and the partial structural model tests.
